核电厂反应堆冷却剂平均温度预测控制及仿真研究  

Protective Control and Simulation Research on Nuclear Power Plant Coolant Average Temperature

作　　者：钱虹[1] 房振鲁 金蔚霄 周蕾[1] 郑鹏远[1] 

机构地区：[1]上海电力学院自动化工程学院,上海200090 [2]上海电气自动化设计研究所有限公司,上海200023

出　　处：《核动力工程》2016年第2期91-96,共6页Nuclear Power Engineering

基　　金：上海市重点实验室资助项目(04DZ05901)

摘　　要：针对核电厂反应堆冷却剂平均温度控制对象,采用冷却剂平均温度的非参数模型,设计动态矩阵控制器(DMC)。采用用于过程控制的对象连接与嵌入(OPC)技术与核电仿真模型连接,构建用于冷却剂平均温度控制仿真研究的平台,在矩阵实验室(MATLAB)环境下针对小范围负荷波动设计动态矩阵预测控制器。仿真得到冷却剂平均温度的跟踪曲线与冷却剂平均温度调节棒(R棒)的变化曲线。通过堆芯轴向功率分布偏差,验证该预测控制算法在满足优化控制性能的同时,保证了反应堆功率分布的安全合理性。The dynamic matrix predictive controller was designed based on the nuclear power plant coolant average temperature and using the non parametric model of the coolant average temperature. Connecting the nuclear power simulation model by the application of the OPC technology, the coolant average temperature control simulation research platform is constructed; In this simulation studies, with the control of dynamic matrix predictive controller and by a small range of load fluctuation, the tracking curve of the coolant average temperature and R bar curve are obtained. The calculation of the axial power distribution in the core deviation proved that the control algorithm can meet the control performance and guarantee the safety and rationality of the reactor power distribution.

关 键 词：冷却剂平均温度 动态矩阵预测控制 变负荷运行 用于过程控制的对象连接与嵌入(OPC) 

分 类 号：TP29[自动化与计算机技术—检测技术与自动化装置]